RS-09-110, Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications

Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications

ML092240199
Person / Time
Site:	LaSalle
Issue date:	08/11/2009
From:	Simpson P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-09-110
Download: ML092240199 (4)

Text

Exelon.

Exelon Nuclear 4300 Winfield Road wwwexeloncorp,corn Nuclear Warrenville, IL 60555 RS-09-110 August 11, 2009 U.S . Nuclear Regulatory Commission ATfN : Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U .S. NRC, "Request for a License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications," dated September 11, 2008 In the referenced letter, Exelon Generation Company, LLC (EGC) requested an amendment to Facility Operating License Nos . NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The proposed amendment removes time, cycle, or modification-related items from the Operating Licenses and Technical Specifications (TS), and corrects a typographical error that was introduced into the TS in a previous amendment.

EGC has identified that the markup of TS page 3.7.1-2 that was provided in the referenced letter contains an error. A revised markup of page 3.7.1-2, with the error corrected, is provided in the Attachment to this letter .

EGC has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of the referenced letter . The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration . In addition, the additional information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

August 1 1, 2009 U .S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Mr . Kenneth M . Nicely at (630) 657-2803 .

I declare under penalty of perjury that the foregoing is true and correct . Executed on the 11th day of August 2009.

Respectfully, Pat'fick R. Simpson 0

Manager - Licensing

Attachment:

Revised Markup of Proposed Technical Specifications Page cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector- LaSalle County Station Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT Revised Markup of Proposed Technical Specifications Page LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGE 3.7.1-2

RHRSW System 3 .7 .1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. ------- NOTE-------- B .I -------- NOTE ---__----

On ; applicable to Enter applicable Unit 2 .. ing Conditions and replacemen tf the Required Actions of Division I CSC LCO 3 .4 .9, "Residu isolation valves Heat Removal ng . . .

during Unit I Shutdown Co Refueling 11 while System-Unit I is in Mode 4,5, Shu wn," for RHR or defueled . down cooling

---

subsy m made One RHRSW subsystem inoperab y RHRSW inoperable . System .

Restore RHRSW r4 days subsystem to OPERABLE status .

,- C- Required Action and 6 .i Be in MODE 3 . 12 hours associated Completion Ti ra of Conditio j A ~"

)not met .

Both RHRSW subsystems 4-t -------- NOTE ---------

inoperable . Enter applicable Conditions and Required Actions of LCO 3 .4 .9 for RHR shutdown cooling subsystems made inoperable by RHRSW System .

Restore one RHRSW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystem to OPERABLE status .

(continued)

LaSalle I and 2 3 .7 . 1-2 Amendment No . 184/171